The following 2 query conditions could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Advisory Committee on the Medical Uses of Isotopes]] OR [[:Atomic Safety and Licensing Board Panel]] OR [[:Document Control Desk]] OR [[:Embark Venture Studio]] OR [[:NRC/ACRS]] OR [[:NRC/ASLBP]] OR [[:NRC/Chairman]] OR [[:NRC/EDO]] OR [[:NRC/FSME]] OR [[:NRC/IS]] OR [[:NRC/OCAA]] OR [[:NRC/OCFO]] OR [[:NRC/OCIO]] OR [[:NRC/OCM]] OR [[:NRC/OE]] OR [[:NRC/OEDO]] OR [[:NRC/OGC]] OR [[:NRC/OI]] OR [[:NRC/OIG]] OR [[:NRC/OIP]] , [[Division::+]]</code>.
MONTHYEARML0429603912004-10-150Issue date: 15 October 2004 Title: ORNL/NRC/LTR-04/18, Electronic Archival of the Results of Pressurized Thermal Shock Analyses for Beaver Valley, Oconee, and Palisades Reactor Pressure Vessels Generated with the 04.1 Version of Favor ML0426603842004-09-170Issue date: 17 September 2004 Title: Reports Detailing Structural Analysis of Corrosion Wastage at Davis Besse ML0335200652003-12-160Issue date: 16 December 2003 Title: Letter to Robert Hardies Regarding Cd Containing Latest Version of NRCs Embrittlement Calibration Database ML0311404972003-04-230Issue date: 23 April 2003 Title: Letter to Sid Powell - Pipe Fracture Encylclopedia NUREG/CR-6783, Transmittal of NUREG/CR-6783, Structural Seismic Fragility Analysis of the Surry Containment2002-12-130Issue date: 13 December 2002 Title: Transmittal of NUREG/CR-6783, Structural Seismic Fragility Analysis of the Surry Containment ML0227704612002-09-270Issue date: 27 September 2002 Title: Evaluation of Reactor Pressure Vessel Nozzle to Hot-leg Piping Bimetallic Weld Joint Integrity for the V.C. Summer Nuclear Power Plant, Figures 21 - 70 ML0227602642002-09-270Issue date: 27 September 2002 Title: Evaluation of Reactor Pressure Vessel Nozzle to Hot-leg Piping Bimetallic Weld Joint Integrity for the V.C. Summer Nuclear Power Plant, Memorandum Dated 09/27/02 - Figure 20 ML0202300262002-01-180Issue date: 18 January 2002 Title: NRC Office of Nuclear Regulatory Research Responses to Comments Provided on Draft Report, GSI-191: Parametric Evaluations for Pressurized Water Reactor Recirculation Sump Performance ML0123405202001-08-220Issue date: 22 August 2001 Title: Request for Expediated Response from Industry on Several Technical Issues Concerning Environmental Qualification of safety-related, low-voltage Instrumentation & Control Cables ML0118600592001-07-030Issue date: 3 July 2001 Title: Transmittal of Draft Technical Report Documenting the Parametric Evaluation of Sump Screen Blockage at Pressurized Water Reactors ML0036808892000-02-050Issue date: 5 February 2000 Title: Draft SNL Letter Report, Circuit Failure Mode and Likelihood Analysis 2004-09-17
MONTHYEARML0426603842004-09-170Issue date: 17 September 2004 Title: Reports Detailing Structural Analysis of Corrosion Wastage at Davis Besse ML0426004552004-09-010Issue date: 1 September 2004 Title: ORNL Report, ORNL/NRC/LTR-04-15, Probabilistic Structural Mechanics Analysis of the Degraded Davis Besse RPV Head ML0426603772004-09-010Issue date: 1 September 2004 Title: ORNL Report, ORNL/NRC/LTR-04/15, Appendix a - B Description of Davis Besse Monte Carlo Damage-State Code ML0426602192004-09-010Issue date: 1 September 2004 Title: ORNL Report, ORNL/NRC/LTR-02/10 Stochastic Failure Model of the Davis-Besse RPV Head ML0426602062004-09-010Issue date: 1 September 2004 Title: ORNL Report, ORNL/NRC/LTR-04/13, Experimental Program for Investigating the Influence of Cladding Defects on Burst Pressure ML0332903762003-11-240Issue date: 24 November 2003 Title: G20030709/LTR-03-0746 - Donna Lueke Ltr. Lessons Learned Task Force; Revisit Petitions for Further Oversight; Revoke Operating License; and Inform Public of the Reactor Pressure Vessel Head Degradation at Davis-Besse ML0332205412003-11-100Issue date: 10 November 2003 Title: Thanks and Request Letter from Citizens of Ottawa County to NRC, Firstenergy, Puco, Elected Officials, Watchdogs, Advocates, Reporters Re Davis-Besse ML0331601062003-07-250Issue date: 25 July 2003 Title: E-mail Press Release 03-099: NRC Finds Indian Point Meets Reasonable Assurance Criteria ML0326009832002-08-140Issue date: 14 August 2002 Title: Stochastic Failure Model for Davis Besse RPV Head ML0220304682002-07-150Issue date: 15 July 2002 Title: Union of Concerned Scientists Continues to Attempt to Understand Factors Contribution to the near-miss loss-of-coolant Accident at Davis-Basse ML0127101032001-09-270Issue date: 27 September 2001 Title: Request for Review of Common-Cause Failure Insights Reports for Emergency Diesel Generators, Pumps, Motor-Operated Valves, and Circuit Breakers 2004-09-17